Text

Amends 85 & 58 to Licenses DPR-70 & DPR-75,respectively, Revising Reactor Trip Block W/Turbine Trip from P-7 (11%) Permissive Up to P-9 (50%) Permissive
	ML20153A879
Person / Time
Site:	Salem
Issue date:	06/27/1988
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
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ML20153A882	List: ML20153A879;
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	NUDOCS 8807120645
	Download: ML20153A879 (14)
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC-CITY ELECTRIC COMPANY COCKET N0. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amen 6 rent No. 85 License No. DPR-70 1.

The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated July 2, 1987 as supplemented July 7, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (1) that the activities authorized by this ainendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulatiens set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:

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. (2) Technical Specifications and Environmental Pro *.:ectkon Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereb: incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the next refueling outage, cycle 8, currently scheduled for April 1989.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

. Changes to the Technical Specifications Date of Itsuance:

June 27, 1988 i

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- (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license. The licensee shall operate the facility in accordance with

- the Technical Specifications.

3.

This license amendment is effective as of the next refueling cutage, cycle 8, currently scheduled for April 1989.

FOR THE NUCLEAR REGt'LATORY COMMISSION

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V Walter R. Butler, Director Project Directorate I-?

Divisinn of Peactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: June 27, 1988

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ATTACHMENT TO LICENSE AMENOMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Pevise Appendix A as follows:

Remove Pages Insert Pages B 2-7 B 2-7 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 t

m LIMITING SAFETY SYSTEM SETTINGS BASES reliability of the Reactor Protection System. This trip is redundant to the Steam Generator Water Level Lw-Low trip. The Steam / Fee &ater Flow Mismatch portion of thig trip is activated when the steam flow exceeds the fee &ater flow by > 1.42 x 100 lbs/ hour. The Steam Generator low Water level portion of the l

trip is activated when the water level drops below 25 percent, as indicated by the narrow range instrument. These trip values include sufficient allwance in excess of normal operating values to preclude spurious trips but will initiate a reactor trip before the steam generators are dry. Therefore, the required capacity and starting time requirements of the auxiliary feedwater pumps are reduced and the resulting thermal transient on the Reactor Coolant System and steam generators is minimized.

Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Underf requency Reactor Coolant Pug bus trips provide reactor core protection against OPE as a result of loss of voltage or underfrequency to more than one reactor coolant pump. The specified set points assure a reactor trip signal is generated before the low flow trip set point is reached. Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients. For undervoltage, the delay is set so that the time required for a signal to reach the reactor trip breakers following the simultaneous trip of two or more reactor coolant pug bus circuit breakers shall not exceed 0.9 seconds.

For underfrequency, the delay is set 50 that the time required for a signal to reach the reactor trip breakers after the underfrequency trip setpoint is reached shall not exceed 0.3 seconds.

l Turbine Trip A Turbine Trip causes a direct reactor trip when operating above P-9.

Each l

of the turbine trips provide turbine protection and reduce the severity of the ensuing transient. No credit was taken in the accident analyses for operation of these trips. Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.

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SALEM - UNIT 1 B 2-7 Amendment No. 85 i!

TABLE 3.3-1 (Continued)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, l

one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL p0WER to below P-8 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Operation below P-8 may continue pursuant to ACTION 11.

ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue providad the inoperable chanr,el is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - With the number of channels CPERA8LE one less than required by the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CON 0! TION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels < 6 x 10~11 the manual block of amps.

sourcs range reactor trip.

P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels 2 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on:

Low impulse chamber pressure channels flow in more than one 2.a pressure equivalent to 11% of primary coolant loop, RATED THERMAL POWER.

reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, and pressurizer high level.

SALEM - UNIT 1 3/4 3-7 Amendment No. 85

e TAB LE 3.3 1 (Continued)

DES IGNAT ION CON 0! TION AND SETPOINT F UNCTION P-8 With 2 of 4 Power Range Neut.on P-8 prevents or defeats Flux channels > 36% of RATED the automatic block of THERMAL POWER.~

reactor trip on low coolant flow in a single loop.

P-9 With 2 of 4 Power Range neutron P-9 prevents or defeats flux channels > 50% RATED the automatic block of THERMA L POWER."'

reactor trip on turbine t ri p.

P-10 With 3 of 4 Power range neutron P-10 prevents or defeats flux channels < 9% of RATED thi manual block of:

THERMA L POWER.

Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.

Provides input to P-7.

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SA LEM - UNIT 1 3/4 3-8 Amendment No. 85 l

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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. ?

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. OPR-75 1.

The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company,(Delmarva Power and Light Company and Atlantic City Electric Company the licensees) dated July 2, 1987, as supplemented July 7, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as ainended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regelations of the Comission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the realth and safety of the put,iic; anc E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the' license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

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% (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. Se, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the next refueling outage, cycle 4, currently scheduled for September 1988.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 27, 1988

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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

58, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specification:.

3.

This license amendment is effective as of the next refueling outage, cycle 4, currently scheduled for September 1988.

FOR THE NUCLEAR REGULATORY COMMISSION

(/

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G Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuarce: June 27, 1988

ATTACHMENT TO LICENSE AMENDMENT fl0. 58 FACILITY OPERATING LICENSE NO. OPR-75 DOCKET NO. 50-311 Revise Appendix A as-follows:

Remove Pages

-Insert Pages B 2-7 8 2-7 3/4 3-7.

3/4 3-7 3/4 3-8 3/4 3-8 l

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LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltage and Underfrequ6ncy - Reactor Coolant pump Busses The Undervoltage and Underfrequency Reactor Coolant Pump bus trips provide reactor core protection against ON8 as a result of loss of voltage or under-frequency to more than one reactor coolant pump.

The specified set points assure a reactor trip signal is generated before the low flow trip set poin*.

is reachod.

Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients. For undsrvoltage, the delay is set to that the time required for a signal to reach the reactor trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall noe exceed 0.9 seconds.

For underfrequency, the delay is set so that the time required for a l signal to reach the reactor trip breakers after the underfrequency trip setpoint is reached shall not exceed 0.3 seconds.

l rurbine Trio A Turbine Trip causes a direct reactor trip when operating above P-9.

(

Each of the turbins trips provide turbine protection and reduce the severity of the ensuing transient. No credit was taken in the accident analyses for operation of these trips.

Their functional capability at the specified trip l

settings is required to enhance the overall reliability of the Reactor Protection System.

Safety Injection Incut from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection. This trip is provided to protect the core in the event of a LOCA. The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.

Reactor Coolant puso Breaker position Trio The Reaci:or Coolant Pump Breaker Position Trips are anticipatory trips l

which provide reactor core protection against CN8 resulting from the opening of any one pump breaker above P-8 or the opening of two or more pump breakers below P-8.

These trips are blocked below P-7.

The open/close position trips assure a reactor trip signal is generated before the low flow trip set point is reached. No credit was taken in the accident analyses for operation of these trips.

Their functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Protection l

System, l

SALEM - UNIT 2 B 2-7 Amendment No. 58 l

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TABLE 3.3-1 (Continued) l ACTION 9 With a channel associated with an operating loop inoperable, I

restore the inoperable channel to OPERA 8LE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months channel associated with an operating loop may; however, one be bypassed for up tc 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per specification 4.3.1.1.

ACTION 10 With one channel inoperable, restore the inoperable channel to OPERA 8LE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below j the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant pumo Breaker Position) setpoint, within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Operation below the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, may continue pursuant to ACTION 11.

ACTION 11 With less than the Minimum Number of Channels OPERABLE, operatieni may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 With the number of channels OPERABLE one less than required by I

the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

REACTOR TRIP SYSTEM INTERLOCKS OESIGNATION CONDITION AND SETP0!NT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels < 6 x 10'11 the manual block of

amps, source range reactor trip.

P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels >11% of RATED the automatic block of l

THERMAL POWER or 1 of 2 Turt;ine reactor trip on: Low impulse chamber pressure channels flow in more than one 2.a pressure equivalent to 11% of primary coolant loop, RATED THERMAL POWER.

reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, and pressurizer high level.

SALEM - UNIT 2 3/4 3 7 Amendment No. 58

TABLE 3.3-1 (Con,tinued)

OESIGNATION CONCITION AND SETp0!NT FUNCTION p-8 With 2 of 4 Power Range Neutron P-8 prevents or defeats Flux channels > 36% of RATED the automatic block of THERMAL POWER.-

reactor trip on low coolant flow in a single loop.

P-9 With 2 of 4 Power range neutron P-9 prevents or defeats flux channels > 50% of RATED the automatic block of THERMAL POWER.-

reactor trip on turbine trip.

P-10 With 3 of 4 Power range neutron P-10 prevents or defeats flux channels < 9% of RATED the manual block of:

THERMAL POWER.

Power range low setpoint reactor trip, Intermediato range reactor trip, and intermediate range rod stops.

Provides input to P-7.

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l SALEM - UNIT 2 3/4 3-8 Amendment No. 58 i

ML20153A879

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